ML20005F808

Forwards Revised Peaking Factor Limit Rept (Pflr) for Unit 1,Cycle 4 Operation.Revs Reflect That Pflr Valid for Cycle Burnup Range of 0 to 17,000 MW Days Per Metric Ton U

ML20005F808
Person / Time
Site:	Sequoyah
Issue date:	01/05/1990
From:	Michael Ray TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9001170278
Download: ML20005F808 (14)

Text

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TENNESSEE VALLEY AUTHORITY j CH ATT ANOOGA, TENNESSEE 37401 l

SN 157B Lookout Place JAN 051990 i

U.S. Nuclear Regulatory' Commission ATTN: Document Control Desk j Hashington, D.C. 20555 Gentlemen: >

In the Matter of ) Docket Nos. 50-327 l Tennessee Valley Authority ) 50-328 SEQUOYAH NUCLEAR PLANT (SON) UNIT 1 - REVISED PEAKING FACTOR LIMIT REPORT (PFLR) FOR UNIT 1 CYCLE 4 OPERATION

Reference:

TVA letter to NRC dated September 11, 1985, regarding SQN Unit 1 Cycle 4 PFLR This letter provides a revised PFLR for SQN's Unit 1 Cycle 4 operation l (Enclosure 1). These revisions reflect that the PFLR is valid for.a cycle ,

burnup range of 0 to 17,000 megawatt days per metric ton uranium (MWD /MTU).

The PFLR transmitted by the reference was valid for a burnup range of 0 to  :

16,000 MHD/MTV. The revised PfLR also reflects the current technical specification limit of the heat flux hot channel factor, fo(z). This report is provided in accordance with SQN Technical Specification 6.9.1.14 " Radial Peaking factor Limit Report."

It should be noted that the reference submitted a superseded copy of the PFLR v coversheet. The W(z) curves submitted by the reference are valid for Unit 1 Cycle 4 burnups between 0 and 16,000 MHD/MTV. A copy of the. letter supporting this burnup range is provided in Enclosure 2.

Please direct questions concerning this issue to Russell R._ Thompson at-(615) 843-7470.

Very truly yours, i TENNESSEE VALLEY AUTHORITY r  :

$, A y,

Mana r, Nucleer' icensing i and Regulatory Affairs i Enclosures cc: See page 2 I i

900117027e 900105 7 PDR ADOCK 0500 .

P L

An Equal Opportunity Ernployer

U.S. Nuclear Regulatory Commission JAN 051990 cc (Enclosures):

Ms. S. C. Black, Assistant Director for Projects TVA Projects Division U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852 Mr. B. A. Wilson, Assistant Director for Inspection Programs TVA Projects Division U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 NRC Resident Inspector Sequoyah Nuclear Plant 2600 Igou Ferry Road i Soddy Daisy, Tennessee 37379 l

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SEQUOYAH NUCLEAR: MANT UNIT 1 CYC1.E 4  ;

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[ Westinghouse Electric Corporotlon Commerciel Nuclear Fuel DMalon

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December 15, 1989  !

. Sp2V* 4-0119 i 6

Mr. T. A. Pet 1) Ltr. 85TV*=G-0075 Manager, Fabriantien ard tmilisation 9/s/85 ,

Tunneases Valley Authority 3) IEr. 892V* 4-0112 1101 Machet Street 11/30/89 j R er sa l Omttanooga, 'Nnnamnea 37401  :

Dear Mr. Huyst >

TD8555EE VAIZET AUDs3G2T l i

l SEQUDDH UNIT 1 crCIE 4 EMNEHf The W(s) functions generated for the sequoyah Unit 1 cycle 4 redanign are  !

valid for the additional 1000 WCHEU constdown. 'Ihe W(s) functions provided in the Sequcynh thit 1 cycle 4 Penking Factor Ihmit Report  ;

(Rafarance 1) may be extrapolated to an and of life bump of

~

(- 17,000 W44CU. A revised oever sheet from the Referenos 1..ywit is enclosed. .

Very truly yours, w I g./. 9%pW eet Engimer j Prcdects NEctkh CC: o. W. h ylor - 1A J. F. Burrow - 2A I G. Gault - 2A D. M. Marks - 3A E I. R..Williamsen - 1A RRCEIVED 7 1 A. Saniale - 3A "* N j l

Dft 181909 '

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I h Feaking Factor Limit Report for Sequoyah Unit 1, Cycle 4 RA00 Operation 1 l .

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-ThisPeakingFactorLimitReportisprovidedinaccordancewith j L Paragraph 6.f 1.9 of'the. sequoyah Unit 1 Technical' specifications.  ;

l The sequoyah Unit 1 Cycle 4 elevation dependent.W(s) values for RAOC operation at beginning,-;early middle, late middle, ano mar end.cf life  ;

are shown in Figures 1 through 4, respectively. . This-information-is .i sufficient to determine W(s)'versus core height for Cycle 4 burnups in  :

the range of 0 MWD /NTU to 17000 MWD /MTU.through the use of three point-interpolation. V(a) was calculated using the method described ~in Part B of Reference 1. j i The appropriate V(s) function is used to confirm that the heat flux hot. h channel factor Sr (s) will be limited to the Technical Specification  ;

values of: s c(

2.d1D I q(s) s P (K(s)) for P > -0.50 and

( Tq (t) s 4.300 [K(z)] fot P -s 0,50 t ,

4 1

p L

1

! 1he appropria.te: elevation _ dependent V(z) values. wnen applied to a '

F power distribution measured ~under: equilibrium conditions, demonstrate that the initia1' conditions assumed in the LOCA are met, along_with-the ECCS acceptance criteria of 10CFR50.46.

(1) WCAP.10217 A, Relaxaticn of Constant Axial Offset Control -

Fq Surveillance Technical Specifications )

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4 ENCLOSURE 2-WESTINGHOUSE ELECTRIC CORPORATION

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CYCLE 4 REDESIGN PEAKING FACTOR LIMIT REPORT l

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85TV*-G-075 September 6, 1985

-Keywords: .TVA PEAKING-FACTOR

. SEQUOYAH-UNITS t

Reference:

CDC 167 Mr. J. W. Hufham, Chief Emergency Preparedness and ~ Protection Branch J Tennessee Valley Authority 1630 Chestnut Street Towers II 5 Chattanooga, TN 37401 i

Dear Mr. Hufham:

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,. TENNESSEE VALLEY. AUTHORITY  ;

SEQUOYAH NUCLEAR PLANT  !

CYCLE 4 REDESIGN PEAKING FACTOR LIMIT-REPORT l 1

The Sequoyah Unit 1 Cycle 4 Redesign Peaking Factor Limit Report

, f provides information which permits the exact detennination of W(z)

( versus core height as a function of cycle burnup. 'This report transmits the elevation dependent W(z) values. These are-to.be used as inputs:to j-define-the appropriate fitting coefficients for W(z) interpolations to be performed as a function of cycle burnup and axial elevation. The W(z) values are appropriate for the Cycle 4 redesign burnup range of 0 L to 16000 MWD /MTU.

Thew (z)functionsforCycle4burnupsof 150, 5000,'9000, and 14000-

, MWD /MTU are Figures 1-4 of this memo. Only Figure 1, the W(z) function at BOL was modified in the. redesign. The remaining function originally .

transmitted in Reference;1 did not change. Using the W(z) funccions shown ;i in Figures 1-4, it is appropriate to determine W(z) values for cycle I burnups between 0 and 16000 MWD /MTU using three point interpolation. 1 For three point. interpolation,' the W(z) values-from the three burnup '

steps closest to the measured burnup are used. A revised plot of the-limiting FQ x Prel points and corresponding envelope is also included for information purposes (Figure 5). -

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- Mr. J. W. Hufham, Chief -

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'If you have any comments or questions please contact me.

Very truly.yours,,

• L. A. Livingston .

Project Engineer, NFD Projects-LAV:mid cc:- J. R. Ratliff - IL, IA J. Wills - IL, 1A

0. W. Taylor - IL, IA:

G. Gault - IL, IA K. Allen - IL, IA~

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Peating Factor Lirrit Report for Sequoyah Unit 1 Cycle 4 RAOC Operation

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This peatipg Factor limit Report is provided in accordance with j Paragraph 6.9.1.9 of the Sequoyah Unit 1 Technical Specifications, a The Sequoyah Unit 1 Cycle 4 elevation dependent W(z) values; for RAOC ,

h operation at beginning early middle, late middle, and near end-of-life j are'shown in Figures 1 throu sufficient to determine W(z)gh 4 respectively. This information is j versus core height for Cycle' 4 burnups in 1 the range of 0 MWD /MTU to 16000 MWD /MTU'through the use of three point .

L interpolation.' W(z) was calculated using the method described.in Part B H of Reference 1. p The appropriate W(z) function is used to confirm that the heat flux hot channel factor F 9 -(z) will be limited to the Technical Specification values of:

2.237 Fq (z) 5 p. [K(z)]forP > 0.50 and

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F(z)5 [K(z)]forP g

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l. The appropriate elevation de' pendent W(z) values, when applied.: to' a. power.

i distribution measured under equilibrium conditions,' demonstrates that the

! initial conditions-assumed-in the LOCA are met, along with.the ECCS

' acceptance criteria-of 10CFR50.46.

(1) WCAP-10216-P-A -Relaxation.of Constant' Axial Offset Control -

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